GB/T 47511-2026压水堆核电厂堆芯燃料管理模式变更的安全论证要求

ICS27.120.20

CCSF65

中华人民共和国国家标准

GB/T47511—2026

压水堆核电厂堆芯燃料管理模式

变更的安全论证要求

Safetyverificationrequirementsforchangesincorefuelmanagement

modeofpressurizedwaterreactornuclearpowerplant

2026⁃04⁃30发布2026⁃11⁃01实施

国家市场监督管理总局

国家标准化管理委员会发布

GB/T47511—2026

目次

前言··························································································································Ⅲ

1范围·······················································································································1

2规范性引用文件········································································································1

3术语和定义··············································································································1

4符号和缩略语···········································································································1

5概述·······················································································································1

6安全论证通用要求·····································································································2

7安全论证内容要求·····································································································2

7.1堆芯燃料管理与核设计·························································································2

7.2事故分析、燃料及系统验证所需参数·········································································3

7.3堆芯功率能力验证·······························································································6

7.4反应堆热工水力设计····························································································6

7.5保护参数与定值评价····························································································6

7.6堆芯余热计算·····································································································6

7.7事故分析与放射性后果评价···················································································6

7.8燃料设计验证·····································································································8

7.9系统容量分析·····································································································8

7.10一回路水化学论证······························································································8

7.11乏燃料贮存水池临界安全分析···············································································8

7.12设备运维周期影响分析························································································8

7.13其他分析与论证内容···························································································9

7.14核电厂文件与模拟机参数修改···············································································9

Ⅰ

GB/T47511—2026

前言

本文件按照GB/T1.1—2020《标准化工作导则第1部分：标准化文件的结构和起草规则》的规

定起草。

请注意本文件的某些内容可能涉及专利。本文件的发布机构不承担识别专利的责任。

本文件由全国核能标准化技术委员会（SAC/TC58）提出并归口。

本文件起草单位：成都核总核动力研究设计工程有限公司、生态环境部核与辐射安全中心、核工业

标准化研究所、中国核动力研究设计院、中核运维技术有限公司、大亚湾核电运营管理有限责任公司、

上海核工程研究设计院股份有限公司。

本文件主要起草人：王丹、李冬生、关仲华、廖鸿宽、李天涯、何彩云、李斌、别业旺、吴飞飞、王青、

王冉旭、陈长、刘同先、黄代顺、潘泽飞、蔡光明、高景辉、王丽华。

Ⅲ

GB/T47511—2026

压水堆核电厂堆芯燃料管理模式

变更的安全论证要求

1范围

本文件规定了压水堆核电厂反应堆堆芯燃料管理模式变更的安全论证要求。

本文件适用于压水堆核电厂反应堆堆芯燃料管理模式变更的安全论证。

2规范性引用文件

下列文件中的内容通过文中的规范性引用而构成本文件必不可少的条款。其中，注日期的引用文

件，仅该日期对应的版本适用于本文件；不注日期的引用文件，其最新版本（包括所有的修改单）适用于

本文件。

GB/T4960.2核科学技术术语第2部分：裂变反应堆

3术语和定义

GB/T4960.2界定的以及下列术语和定义适用于本文件。

3.1

关键安全参数keysafetyparameter

与反应堆安全有关的、燃料管理模式变更可能会引起变化的重要参数。

注：关键安全参数包括通用关键安全参数和特定关键安全参数。这些关键安全参数的变化有可能影响正常运行和

事故工况的后果。

4符号和缩略语

下列符号和缩略语适用于本文件。

FQ：热流密度峰因子

N

FΔH：核焓升热通道因子

pH：氢离子浓度指数

ATWS：未能紧急停堆的预期瞬态（Anticipatedtransientswithoutscram）

DNBR：偏离泡核沸腾比（Departurefromnucleateboilingratio）

FSAR：最终安全分析报告（Finalsafetyanalysisreport）

LOCA：冷却剂丧失事故（Lossofcoolantaccident）

PCI：燃料芯块与包壳相互作用（Pellet⁃claddinginteraction）

RCCA：控制棒组件（Rodc